Abstract
coating for Zr-2.5Nb alloy from hydrogenation. Dense TiNx films were prepared by filtered cathodic vacuum arc (CVA). Hydrogen absorption rate was calculated from the kinetic curves of hydrogen sorption at elevated temperature of the sample (T = 673 K) and pressure (P = 2 atm). Results revealed that TiNx films significantly reduced hydrogen absorption rate of Zr-2.5Nb.
Highlights
Zirconium-based alloys such as Zr–1Nb, Zr–2.5Nb are widely used in nuclear industry as cladding materials for Russian PWR of VVER type reactors
It was previously found that TiNx films deposited by direct current magnetron sputtering significantly reduced hydrogen uptake by Zr–1Nb alloy and it is promising films to protect zirconium alloys from hydrogen embrittlement [19, 20]
In this paper we described the influence of TiNx deposited by filtered Cathodic vacuum arc (CVA) onto Zr–1Nb alloy on hydrogen absorption rate and element distribution before and after hydrogen saturation
Summary
Zirconium-based alloys such as Zr–1Nb, Zr–2.5Nb are widely used in nuclear industry as cladding materials for Russian PWR of VVER type reactors. TiNx is a promising candidate as a diffusion barrier coating It has high melting temperature, high hardness, excellent exhibited ion-irradiation tolerance and high thermal conductivity [14,15,16,17]. It was previously found that TiNx films deposited by direct current magnetron sputtering (dcMS) significantly reduced hydrogen uptake by Zr–1Nb alloy and it is promising films to protect zirconium alloys from hydrogen embrittlement [19, 20]. Hydrogen absorption kinetics by Zr–1Nb alloy with TiNx films deposited by filtered CVA have not been discussed. In this paper we described the influence of TiNx deposited by filtered CVA onto Zr–1Nb alloy on hydrogen absorption rate and element distribution before and after hydrogen saturation
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